Zobrazeno 1 - 10
of 45
pro vyhledávání: '"Kazumi Ozawa"'
Autor:
Tamaki Shibayama, Teruya Tanaka, Takehiko Yokomine, Akira Kohyama, Tatsuya Hinoki, Kazumi Ozawa, Chang Ho Park, Tomitsugu Taguchi, Yasushi Yamamoto, Akira Hasegawa, Shuhei Nogami, Sosuke Kondo, Ryuta Kasada, Hirotomo Iwakiri, Masatoshi Kondo, Tomoaki Kunugi, Tatsuo Shikama, Nariaki Okubo, Hiroyasu Tanigawa, Satoshi Konishi, Joon-Soo Park, Toyohiko Yano, Bun Tsuchiya, Shinji Nagata, Takashi Nozawa, Yoshitaka Ueki
Publikováno v:
Journal of Nuclear Materials. 511:582-590
The R&D on SiC/SiC composites under the broader approach (BA) activities between Japan and the EU for fusion DEMO developed a fundamental database of mechanical (Task-1) and physical/chemical (Task-2) properties, with a primary target of the applicat
Autor:
Kiyohiro Yabuuchi, Hiroyasu Tanigawa, Kazumi Ozawa, Makoto Fukuda, H. Usami, Akira Hasegawa, Shuhei Nogami, Taehyun Hwang
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 430-435 (2016)
The irradiation hardening and microstructures of pure W and W – 3%Re for up to 5.0 dpa by self-ion irradiation were investigated in this work. The ion irradiation was conducted using 18 MeV W6+ at 500 and 800 °C. A focused ion beam followed by ele
Autor:
Takaaki Koyanagi, Kazuya Shimoda, Tatsuya Hinoki, Yutai Katoh, Kazumi Ozawa, Lance Lewis Snead
Publikováno v:
Journal of Nuclear Materials. 478:97-111
Irradiation creep beyond the transient regime was investigated for various silicon carbide (SiC) materials. The materials examined included polycrystalline or monocrystalline high-purity SiC, nanopowder sintered SiC, highly crystalline and near-stoic
Publikováno v:
Fusion Engineering and Design. :2054-2057
In order to examine the impacts of friction stir processing (FSP) on irradiation effects in vacuum-plasma-spray (VPS) coated tungsten (W), nano indentation hardness was evaluated of three kinds of W materials after self-ion-irradiation to 5.0–5.4 d
Publikováno v:
Fusion Engineering and Design. :2080-2084
Tungsten (W) is the primary candidate material as a plasma facing material in fusion devices, as for its high melting temperature, good thermal conductivity and low sputtering rate, and vacuum plasma spray (VPS) technique is preferred as it is applic
Autor:
Takashi Nozawa, Wallace D. Porter, Chunghao Phillip Shih, Yutai Katoh, Lance Lewis Snead, Takaaki Koyanagi, Kazumi Ozawa
Publikováno v:
Journal of Nuclear Materials. 462:450-457
Nuclear-grade silicon carbide (SiC) composite material was examined for mechanical and thermophysical properties following high-dose neutron irradiation in the High Flux Isotope Reactor at a temperature range of 573–1073 K. The material was chemica
Publikováno v:
Acta Materialia. 83:1-9
Composites consisting of a SiC matrix prepared by chemical vapor infiltration that was reinforced by Tyranno™ SA 3rd (TSA3) or Hi-Nicalon™ Type S (HNLS) SiC fibers were irradiated with 5.1 MeV Si ions to 100 dpa at 300 °C. It was confirmed that
Publikováno v:
Journal of Nuclear Materials. 455:73-80
The irradiation creep behavior of nano-powder sintered silicon carbide was investigated using the bend stress relaxation method under neutron irradiation up to 1.9 dpa. The creep deformation was observed at all temperatures ranging from 380 to 1180
Publikováno v:
Journal of Nuclear Materials. 455:549-553
Understanding the cracking process of the composites is essential to establish the design basis for practical applications. This study aims to investigate the damage accumulation process and its anisotropy for nano-infiltration transient eutectic sin
Publikováno v:
Fusion Engineering and Design. 89:1723-1727
To identify a comprehensive stress envelope, i.e., strength anisotropy map, of silicon carbide fiber-reinforced silicon carbide matrix composite (SiC/SiC composite) for practical component design, tensile and compressive tests were conducted using th